Criticality data and validation studies of arrays of mixed-oxide fuel pins in aqueous and organic solutions

Journal Article · Thu Sep 01 04:00:00 EDT 1994 · Nuclear Technology; (United States)

OSTI ID:6903596

Smolen, G R ^[1]; Bierman, S R ^[2]; Fukumura, Nobuo ^[3]

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1. Oak Ridge National Lab., TN (United States). Computing and Telecommunications Div.
2. Pacific Northwest Lab., Richland, WA (United States)
3. Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)

Critical experiments were conducted with organic- and water-moderated arrays of mixed plutonium and uranium oxide fuel pins. The organic solution consisted of 32 vol% tributyl phosphate and 68 vol% normal paraffin hydrocarbon. The square lattice pitches ranged from 0.761 to 1.935 cm. A direct comparison between the reactivity of the two systems was not possible, because most of the experiments conducted with water were performed [approximately]7 yr before the organic solution experiments. At the two lattice pitches where a direct comparison could be made, based on the number of fuel pins required for criticality, it was determined that the reactivity of the water-moderated system was the same or slightly higher than the organic-moderated system. These data were used in calculational studies performed independently at the Oak Ridge National Laboratory (ORNL) and the Power Reactor and Nuclear Fuel Development Corporation of Japan (PNC) with the KENO-IV computer code. A 27-energy-group cross-section library derived from the Evaluated Nuclear Data File B-Version IV (ENDF/B-IV) was used in both studies. The results of these analyses are in good agreement with the experimental results with calculated k[sub eff]'s ranging from 0.991 to 1.014. The average calculated k[sub eff]'s based on the ORNL and PNC analyses were 1.001 and 1.004, respectively. No trends in calculated k[sub eff] with any parameters were identified.

• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6903596
• Journal Information: Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 107:3; ISSN 0029-5450; ISSN NUTYBB
• Country of Publication: United States
• Language: English

Related Subjects

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054000* -- Nuclear Fuels-- Health & Safety
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
420203 -- Engineering-- Handling Equipment & Procedures
ASIA
COMPUTER CODES
COOPERATION
CRITICALITY
DATA ANALYSIS
DEVELOPED COUNTRIES
FUEL ELEMENTS
FUEL PINS
FUEL REPROCESSING PLANTS
FUELS
INTERNATIONAL COOPERATION
JAPAN
K CODES
MIXED OXIDE FUELS
MODERATORS
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
PUREX PROCESS
REACTOR COMPONENTS
REPROCESSING
SAFETY ANALYSIS
SEPARATION PROCESSES
SOLID FUELS
TESTING
US DOE
US ORGANIZATIONS
VALIDATION